ML20154P624

Insp Repts 50-348/88-16 & 50-364/88-16 on 880419-21.No Violations or Deviations Noted.Major Areas Inspected:Environ Qualification of Electrical Equipment & Followup of Unresolved Items

ML20154P624
Person / Time
Site:	Farley
Issue date:	05/17/1988
From:	Conlon T, Merriweather N, Paulk C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20154P622	List: ML20154P618 ML20154P624
References
50-348-88-16, 50-364-88-16, NUDOCS 8806060014
Download: ML20154P624 (6)

See also: IR 05000348/1988016

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UNITED STATES

[pa Qte RUCLEAR REGULATORY COMMISSION

8. 7

REGION il

$ 101 MARIETTA STRE ET, N.W.

• 1 * ATLANTA, GEORGI A 30323

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Report Nos.: 50-348/88-16 and 50-364/88-16

Licensee: Alabama Power Company

600 North 18th Street

Birmingham, AL 35291-0400

Docket Nos.: 50-348 and 50-364 License Nos.: NPF-2 and NPF-8

Facility Name: Farley 1 and 2

Inspection Conduc ed: April 19-21,1983

Inspectors: _ J2#W'# " N /7- M

N. /Nerriwea ther Date Signed

b djk- 6- o- es

C.,PauW Date Signed

Accompanying Personnel: T. E. Conlon

Approved by:.T.'E. Conlon, Section Chief'

rwh [ 7 ~k

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Date Signed

Plant Systems Section

Division of Reactor Safety

SUMMARY

Scope: This special, announced inspection was in the area of Environmental

Qualification (EQ) of Electrical Equipment and involved followup on Unresolved '

Items 50-348, 364/87-30-04, 10 and 12 and Violation. 50-348, 364/87-30-15.  ;

Results: No violations or deviations were identified.

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8806060014 880519 'i ,

POR ADOCK 05000348 -l

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REPORT DETAILS

1. Persons Contacted

Licensee Employees

• S. Fulmer, Supervisor, Safety Audit Engineering Review

• J. Garlington, Manager, Engineering and. Licensing

• D. H. Jones, Manager, Nuclear Engineering

• W. B. Shipman, Assistant Plant Manager - Support

• J. D. Woodard, General Manager, FNP

Other Organization

• J. Love, Assistant Project Engineer, Bechtel Engineering

• J. E. Sundergil, EQ Group Supervisor, Bechtel Engineering

NRC Resident Inspectors

W. Bradford, Senior Resident Inspector

• • W. Miller, Resident Inspector

• Attended exit interview

• • Attended entrance meeting on April 19, 1988

2. Exit Interview

The inspection scope and findings were summarized on April 21, 1988, with

those persons indicated in paragraph 1 above. The inspectors described No

the areas inspected and discussed in detail the inspection findings.

However, the

dissenting comments were received from the licensee. i

licensee did make certain commitments which are discussed in Paragraphs _3.a l

and 3.d.

The licensee did identify some material as proprietary during this

inspection, but this material is not included in this inspection report.

3. Licensee Action on Previous Enforcement Matters

a. (0 pen) Violation 50-348,364/87-30-15, Raychem/ Chico-A Seals

A previous inspection had identified the licensee's failure to

establish qualification for the Raychem/ Chico-A seals for moisture

barriers on Namco Limit Switches both inside containment and in the

Main Steam Room (MSR). Subsequent to that inspection, the licensee

provided additional information which indicated that the seal design

used in the MSR was different from the one used insideneither

However, containment

design in

that no Chico-A sealing compound was used.

was shown to be qualified to the 00R Guidelines or NUREG OS88, CAT

II criteria. Additional test data was provided which indicates that

the design with the Raychem boot used in the MSR was tested for

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submergence at' 212 F for four hours and a cooldown and soakThis of 20

hours at a pressure head of approximately ten feet (5 psig).-

test data -was not adequate to demonstrate qualifications for Main

Steam Line Break accident in the MSR with peak temperatures of

approximately 326 F.

In a letter dated April 4,1988, - APC0 comitted to replace all

Raychem/ Chico-A seals on Namco limit switches inside Unit.1

containment prior to restart from the current _ refueling outage.

Additionally, APC0 committed to' replace these same seals in Unit 2

During

containment during the next ou: age of sufficient. duration.

this inspection APC0 committed to install an acceptable cable

entrance configuration for the Namco Limit Switches in the MSR's

Furthermore, APC0on

both units during the next refueling outage.

committed to provide a justification for continued operations for-

Units 1 and 2 to the NRC for evaluation and acceptance prior to

Unit I restart.

The previously identified violation is still open and being e. valuated

for escalated enforcement.

b. (Closed) Unresolved Item 50-348, 364/87-30-04, Failure to Train

Personnel Involved in EQ Activities in the Requirements of the EQ

Program.

Actions taken by the licensee to resolve this issue were discussed

during the enforcerrent conferent e held in the NRC Region II office on

March 15, 1988. In this meeting, the licensee stated that the

following imediate corrective actions had been implemented:

Plant training plan has been revised to require training for

Technical Staff and Managers

' The FNP QC engineer and his staff, and the Plant Modifications

group have been trained on EQ

Appropriate General Office Staff personnel have also been

trained on EQ

Licensed operator will be trained as part of upcoming requali-

fication training

A review of training attendance sheets confirmed the implementation

of the corrective action. Based on the above, this item is

considered closed.

c. (Closed) Unresolved Item 50-348,364/87-30-10, Raychem Stilan Cable

This cable was not considered qualified during the inspection because

the IR values given in the report have no meaning. Subsequent to that

inspection the licensee provided information on their commitments to

the commission to meet Regulatory -Guide 1.97. In a letter dated

June 12, 1984, from NRC, S. Varga to Mr. R. P. Mcdonald, the

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confirmatory order based on certain APC0

Commission issued a

The order required APC0 to implement RG 1.97 require-

commitments.

ments on Unit 1 by March 1988, and on Unit 2 by October 1987.

The licensee stated thatcable

The Stilan the Stilan Cable

has been was as

replaced added tothe-

part of the EQ Master

list by error.

Reg. Guide 1.97 upgrade for Unit 2 and will be. replaced on Unit i

during the eighth refueling outage.

This item is, therefore, considered closed.

d. (0 pen) Unresolved Item 50-348, 364/87-30-12, Certain S0Vs may not be

Qualified Due to a Lack of Cable Entrance Seals.

A major environmental qualification concern involves the absence of

cable entrance seals on Automatic Switch Company (ASCO) Solenoid

valves that are required to be energized and/or cycled during a

design basis accident. The valves effected by this concern are

A detail description

located both inside containment and the MSR.

of these valves is included in Appendix A to'this report.

The NRC inspe . ors reviewed ASCO test reports (AQS 21678/TR Rev. A

and AQR-67368/Rev.1), FRC Test Report (NUREG 3424) and GPC The Hatch

Test Report on LOCA/MSLB Testing of ASCO solenoid valves.

inspectors concluded that the ASCO reports by themselves did not The

adequately address the anomalies due to moisture intrusion.

Franklin report was inconclusive as to whether ASCO housings were

seal tight under LOCA conditions because they did not use a known

qualified seal configuration. The only test report that obtained

However, there

good results appeared to be the GPC Hatch Report. Based on review of

still remained some questions with this report.

the above, the inspectors concluded that Farley's ASCO configurations

were not qualified because they had not adequately addressed the

anomalies caused by moisture intrusion. Therefore, to_ resolve this

concern ADC0 proposed the following corrective actions:

(1) APC0 will developThis

a JC0 for S0Vs required for long term

JC0 will consider existing . test data, farley

operation.

configuration and short duration environmental profile for the

MSR. APC0 will submit the JC0 to NRC for evaluation and

acceptance.

(2) APC0 will modify the existing conduit configuration on both i

units in the MSRs to permit when possible moisture drainage away

from the solenoid housing. Those in Unit I will be modified l

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prior to plant restart,

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(3) APC0 will develop a JCO for.five S0Vs requiredThe for long term

JC0 will be

operations inside Units 1 and 2 containments. formulated to me

prior to restart of Unit I to NRC for evaluation and acceptance.

APC0 will modify the flex conduit on one.PORY S0V, inside Unit I

(4)

containment, to provide for moisture drainage. This also will

be completed prior to Unit I restart.

The inspectors examined S0V installations in the MSR on Unit 1--and

reviewed photographs of all ten long term S0V containment configura-

tions. ~ The inspectors concluded that these configurations are

somewhat similar to what was tested by ASCO in the above testThis

reports, however, the anomalies were not adequately addr

completion of proposed long term corrective actions.

4. Unresolved Items

Unresolved items were not identified during this inspection.

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APPENDIX A

LIST OF ASCO SOLEN 010 VALVES WITHOUT CABLE ENTRANCE SEALS

Component Equipment Function Location Comments

N11SV3369AC-A Main Steam Isolation MSR Note 1

N11SV3369BC-A Main Steam Isolation MSR Note 1

N11SV3369CC-A Main Steam Isolation MSR Note 1

N11SV3370AC-B Main Steam Isolation MSR Note 1

N11SV3370BC-8 Main Steam Isolation MSR Note l'

N11SV3370CC-B Main Steam Isolation MSR Note 1

N11SV3916A-B Main Steam Bypass MSR Note 1

N11SV397L3-8 Main Steam Bypass MSR Note 1

N12SV3235A-AB Steam Admission to Turbine MSR Note 1

Driven Auxiliary Feedwater

(TDAFW)

N12SV3235B-AB Steam Admission to TDAFW MSR Note 1

N235V3227AA-A Motor Driven (MD) AFW Flow MSR Note 2

Control

N23SV3227AC-B MD AFW Flow Control MSR Note 2

N23SV3227BA-A MD AFW Flow Control MSR Note 2

N23SV3227BC-8 MD AFW Flow Control MSR Note 2

N23SV3226CA-A MD AFW Flow Control MSR Note 2

N23SV3227CC-B MD AFW Flow Control MSR Note 2

N23SV3228AA-AB TD AFW Flow Control MSR Note 2

N23SV3228BA-AB TD AFW Flow Control MSR Note 2

N23SV3228CA-AB TD AFW Flow Control MSR Note 2

831SV0444BA-B Pressurizer (PZR) P0RV CTMT Note 2

B31SV0444BA-A PZR PORY CTMT Note 2

831SV0445AA-A PZR PORV CTMT Note 2

B31SV0445AB-A PZR PORV CTMT Note 2

P17SV3184-B RCP CCW CTMT Note 3

Note 1: Energized, does not change state during accident

Note 2: Changes state periodically during accident

Note 3: Energized on a Phase B isolation.

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